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Issues
January 2015
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Editorial
Editorial
ASME J of Nuclear Rad Sci. January 2015, 1(1): 010201.
doi: https://doi.org/10.1115/1.4029141
Topics:
China
,
Design
,
Nuclear engineering
,
Nuclear fuel cycle
,
Nuclear power
,
Nuclear power stations
,
Nuclear reactors
,
Physics
,
Radiation (Physics)
,
Risk
NED Chair’s Message
ASME J of Nuclear Rad Sci. January 2015, 1(1): 010202.
doi: https://doi.org/10.1115/1.4029140
Guest Editorial
Professor Geoffrey Hewitt on His 80th Birthday
ASME J of Nuclear Rad Sci. January 2015, 1(1): 010301.
doi: https://doi.org/10.1115/1.4029139
Topics:
Engineering teachers
Research Papers
Nuclear Power as a Basis for Future Electricity Generation
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011001.
doi: https://doi.org/10.1115/1.4029420
Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011002.
doi: https://doi.org/10.1115/1.4026389
Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011003.
doi: https://doi.org/10.1115/1.4026391
Topics:
Computational fluid dynamics
,
Coolants
,
Energy generation
,
Fuels
,
Graphite
,
Heat flux
,
Laminar flow
,
Temperature
,
Turbulence
,
Wall temperature
Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011004.
doi: https://doi.org/10.1115/1.4026392
Topics:
Creep
,
Design
,
Failure
,
Fatigue
,
Fracture (Materials)
,
In-service inspection
,
Probability
,
Reliability
,
Safety
,
Stress
Experimental Modeling of Wind-Driven Bin-by-Bin Resuspension Factors of Freshly Fallen Radionuclides After an Energetic Release From a Radiological Dispersal Device
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011005.
doi: https://doi.org/10.1115/1.4026390
Study on Neutronics and Thermalhydraulics Characteristics of 1200-MWel Pressure-Channel Supercritical Water-Cooled Reactor
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011006.
doi: https://doi.org/10.1115/1.4026387
Topics:
Computational fluid dynamics
,
Coolants
,
Fuels
,
Pressure
,
Supercritical water reactors
,
Temperature
,
Water
,
Heat transfer
,
Heat flux
Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011007.
doi: https://doi.org/10.1115/1.4026394
Topics:
Accidents
,
Coolants
,
Design
,
Flow (Dynamics)
,
Fuels
,
High temperature
,
Temperature
,
Transient analysis
,
Transients (Dynamics)
,
Heat transfer
Study on Specifics of Forced-Convective Heat Transfer in Supercritical Carbon Dioxide
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011008.
doi: https://doi.org/10.1115/1.4026395
Topics:
Carbon dioxide
,
Errors
,
Heat transfer
,
Supercritical carbon dioxide
,
Temperature
,
Water
,
Fluids
,
Heat flux
Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011009.
doi: https://doi.org/10.1115/1.4026401
Topics:
Equilibrium (Physics)
,
Fuels
,
Graphite
,
Molten salt reactors
,
Neutrons
,
Nuclear fuel cycle
,
Design
,
Nuclear fission
,
Uranium
Technical Brief
A Note on Mixture Density Using the Shannak Definition
ASME J of Nuclear Rad Sci. January 2015, 1(1): 014501.
doi: https://doi.org/10.1115/1.4026388
Topics:
Density
,
Microchannels
,
Pipes
,
Pressure gradient
,
Flow (Dynamics)
Email alerts
RSS Feeds
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